ML090640224
| ML090640224 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 03/26/2009 |
| From: | James Kim Plant Licensing Branch 1 |
| To: | Entergy Nuclear Operations |
| kim J, NRR/ADRO/DORL, 415-4125 | |
| References | |
| TAC ME0241 | |
| Download: ML090640224 (11) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 M=rrch /.6, zr>>
Site Vice President Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508 SUB~IECT:
PILGRIM NUCLEAR POWER STATION - ISSUANCE OF AMENDMENT RE:
TECHNICAL SPECIFICATION CHANGE CONCERNING SAFETY LIMIT MINIMUM CRITICAL POWER RATIO (TAC NO. ME0241)
Dear Sir or Madam:
The Commission has issued the enclosed Amendment No. 232 to Facility Operating License No. DPR-35 for the Pilgrim Nuclear Power Station. This amendment is in response to your application dated December 16, 2008, as supplemented by letter dated February 19, 2009.
The amendment would revise the Technical Specifications (TS) Section 2.1.2, Safety Limit Minimum Critical Power Ratio (SLMCPR) for two-loop and single-loop operation.
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register Notice.
Sincerely,
?~
James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-293
Enclosures:
- 1. Amendment No.
232 to License No. DPR-35
- 2. Safety Evaluation cc w/encls: Distribution via ListServ
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ENTERGY NUCLEAR GENERATION COMPANY ENTERGY NUCLEAR OPERATIONS, INC.
DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATIOI\\!
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 232 License No. DPR-35
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by Entergy Nuclear Operations, Inc. (the licensee) dated December 16, 2008, as supplemented by letter dated February 19, 2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's requlations and all applicable requlrements have been satisfied.
-2
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-35 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 232,are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of the date of issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION Mark G. Kowal, Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the License and Technical Specifications Date of Issuance: ~tlrch 26, '2!J:f}
ATTACHMENT TO LICENSE AMENDMENT NO.232 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 Replace the following page of the Facility Operating License with the attached revised page.
The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove 3
Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Insert 2-1 2-1
- 3 B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 232,are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
C.
Records ENO shall keep facility operating records in accordance with the requirements of the Technical Specifications.
D.
Equalizer Valve Restriction - DELETED E.
Recirculation Loop Inoperable - DELETED F.
Fire Protection ENO shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated December 21, 1978 as supplemented subject to the following provision:
ENO may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
G.
Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Pilgrim Nuclear Power Station Physical Security, Training and Qualification, and Safeguards Contingency Plan, Revision 0" submitted by letter dated October 13, 2004, as supplemented by letter dated May 15, 2006.
Amendment 225, 226, 227, 228, 229, ~,~, 232
2.0 SAFETY LIMITS 2.1 Safety Limits 2.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10% of rated core flow:
THERMAL POWER shall be 525% of RATED THERMAL POWER.
\\
2.1.2 With the reactor steam dome pressure z 785 psig and core flow z 10% of rated core flow:
MINIMUM CRITICAL POWER RATIO shall be z 1.08 for two recirculation loop operation and ~ 1.11 for single recirculation loop operation.
2.1.3
. Whenever the reactor is in the cold shutdown condition with irradiated fuel in the reactor vessel, the water level shall not be less than 12 inches above the top of the normal active fuel zone.
2.1.4 Reactor steam dome pressure shall be 5 1325 psig at any time when irradiated fuel is present in the reactor vessel.
2.2 Safety Limit Violation With any Safety Limit not met within two hours the following actions shall be met:
2.2.1 Restore compliance with all Safety Limits, and 2.2.2 Insert all insertable control rods.
Amendment No. 16,27,42,72,133,146,171,191,219,223,232 2-1
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- i' SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.232TO FACILITY OPERATING LICENSE NO. DPR-35 ENTERGY NUCLEAR GENERATION COMPANY ENTERGY NUCLEAR OPERATIONS, INC.
PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293
1.0 INTRODUCTION
By letter dated December 16, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML083530599), as supplemented by letter dated February 19, 2009 (ML090630422), Entergy Nuclear Operations, Inc. (the licensee) requested changes to the Technical Specifications (TSs) for the Pilgrim Nuclear Power Station (Pilgrim). The amendment changes would revise the numeric values of Safety Limit Minimum Critical Power Ratio (SLI\\J1CPR) in TS Section 2.1.2 from 1.06 to 1.08 for two recirculation loop operation (TLO) and from 1.08 to 1.11 for single recirculation loop operation (SLO).
On the basis of the calculations for Pilgrim core reload analysis for Operating Cycle 18, the calculated SLMCPR increases from 1.06 to 1.08 for TLO and SLMCPR increases from 1.08 to 1.11 for SLO. Accordingly, TS Section 2.1.2 is revised to read as follows:
MINIMUM CRITICAL POWER RATIO shall be ~ 1.08 for two recirculation loop operation and ~ 1.11 for single recirculation loop operation.
In addition, References 5 and 6 from the BASES of Section 2.0 SAFETY LIMITS are deleted since the TS Section 5.6.5.b.1 includes the enveloping reference to NEDE-24011-P-A "General Electric Standard Application for Reactor Fuel" (GESTAR II), Amendment 22, based upon which a fuel reload analysis was performed for Operating Cycle 18. The changes made in the BASES are provided for information only.
2.0 REGULATORY EVALUATION
It is stated in Title1 0 of the Code of Federal Regulations (10 CFR) Section 50.36 that the Safety Limits (SL) are limits on important process variables that are found to be necessary to reasonably protect the integrity of certain physical barriers that guard against the uncontrolled release of radioactivity. The SLMCPR is an SL that is required to be in TSs to ensure that fuel design limits are not exceeded. Pilgrim TS 2.1.2 contains the unit SLMCPR limit, which can vary from cycle to cycle. An NRC-approved methodology, contained in GESTAR II, NEDE-24011-P A, "General Electric Standard Application for Reactor Fuel," Amendment 22, is used to determine the cycle-specific limit to be listed in TS 2.1.2.
- 2 NUREG-0800, "Standard Review Plan for the Review of Safety Analyses Reports for Nuclear Power Plants," Section 4.4, "Thermal and Hydraulic Design," states that the critical power ratio (CPR) is to be established such that at least 99.9 percent of fuel rods in the core would not be expected to experience departure from nucleate boiling or boiling transition during normal operation or anticipated operational occurrences.
The Nuclear Regulatory Commission (NRC) staff review finds that the information provided in the licensee's submittal is consistent with the regulatory requirements.
3.0 TECHNICAL EVALUATION
As stated earlier, the SLMCPR numeric values in TS 2.1.2 are SLs. The SLMCPR limit is established such that at least 99.9% of the fuel rods in the core would not be expected to experience the onset of transition boiling as a result of normal operation and transients, which in turn ensures fuel cladding damage does not occur. The SLMCPR limit is established such that fuel design limits are not exceeded during steady state operation, normal operational transients, and abnormal operational transients. As such, fuel damage is calculated not to occur if the limit is not violated. However, because fuel damage is not directly observable, a step back approach is used to establish corresponding IV1CPR operating limits. The operating limit MCPR (OLMCPR) is established by summing the cycle-specific core reload transient analyses adders and the calculated SLMCPR values. The OLMCPR are required to be established and documented in the Core Operating Limits Report (COLR) for each reload cycle by TS 5.6.5, COLR.
The absolute value of SLMCPR tends to vary cycle-to-cycle, typically due to the introduction of improved fuel bundle types, changes in fuel vendors, and changes in core loading pattern.
Following the determination of the cycle-specific SLMCPR values, the OLMCPR values are derived. The cycle-specific SLMCPR numeric values are listed in TS 2.1.2, and therefore, must be revised using the license amendment process.
Global Nuclear Fuel (GNF) performed the Pilgrim Cycle 18 SLIV1CPR calculation consistent with NRC-approved methodologies and uncertainties, as documented in licensing topical reports (LTRs), NEDE-24011-P-A "General Electric Standard Application for Reactor Fuel," Revision 16 (GESTARII), and the following LTRs:
NEDC-32601 P-A "Methodology and Uncertainties for Safety Limit MCPR Evaluations,"
August 1999.
NEDC-32694P-A "Power Distribution Uncertainties for Safety Limit MCPR Evaluations,"
August 1999.
NEDC-32505P-A "R-Factor Calculation Method for GE 11, GE 12 and GE 13 Fuel,"
Revision 1, July 1999.
NEDO-1 0958-A "General Electric BWR [boiling water reactor] Thermal Analysis Basis (GETAB): Data, Correlation and Design Application," January 1977.
On the basis of the analysis performed by GNF, the licensee has proposed to amend the Pilgrim TS Section 2.1.2 to revise the SLMCPR for the Operating Cycle 18. Cycle 18 will commence from the restart of Refueling Outage (RFO) 17. RFO-17 is scheduled to start on or about April 17, 2009, and restart from the outage is expected on or about May 17, 2009. Cycle 18 core
- 3 design includes 156 new GNF2 fuel types, and the remaining fuels are GE14. Core fuel fraction for Cycle 18 is approximately 27% GNF2 fuel and 73% GE14 fuel. The previous operating cycle (Cycle 17) core design consisted of all GE14 fuels.
Bya letter dated August 29,2008, GNF submitted to the NRC a Report titled, "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II), t\\lEDC-333270P, Revision 1." This NRC-approved report provides generic information relative to the GNF2 fuel design and analysis applicable to BWRs.
The current required SLlVlCPR value in Pilgrim TS is 1.06. Calculations performed by GNF for Cycle 18 resulted in a minimum calculated value of SLMCPR to be 1.08 for TLO, and 1.11 for SLO. For Cycle 18, the limiting SLMCPR occurs at the rated core flow condition. GNF's calculation of the revised plant-specific SLMCPR numeric values for Pilgrim's Cycle 18 was performed as part of the reload licensing analysis for Pilgrim Cycle 18 and is based upon NRC approved methods, and hence it is acceptable. The proposed deletion of References 5 and 6 from the BASES are administrative because the reference included in TS 5.6.5.b.1 envelops these references, and is acceptable.
In consideration of the information provided in the licensee's application and its supplement, as summarized in this safety evaluation, the NRC staff has concluded that the licensee's proposed amendment to update the TS to include cycle-specific SLMCPR numeric values is consistent with the regulatory requirements, and is acceptable. The licensee is authorized to change the SLMCPR as existing in TS 2.1.2 from 1.06 to 1.08 for dual-loop recirculation, and from 1.08 to 1.11 for single-loop recirculation, at steam dome pressures greater than 785 psig and at core flows greater than 10% of rated core flow.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Massachusetts State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (74 FR 4250). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
- 4
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: M. Razzaque Date: Mmh 2h, '2[JJj
March 26, 2009 Site Vice President Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508
SUBJECT:
PILGRIM NUCLEAR POWER STATION - ISSUANCE OF AMENDMENT RE:
TECHNICAL SPECIFICATION CHANGE CONCERNING SAFETY LIMIT MINIMUM CRITICAL POWER RATIO (TAC NO. ME0241)
Dear Sir or Madam:
The Commission has issued the enclosed Amendment No. 232 to Facility Operating License No.
DPR-35 for the Pilgrim Nuclear Power Station. This amendment is in response to your application dated December 16, 2008, as supplemented by letter dated February 19, 2009.
The amendment would revise the Technical Specifications (TS) Section 2.1.2, Safety Limit Minimum Critical Power Ratio (SLMCPR) for two-loop and single-loop operation.
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register Notice.
Sincerely, IRAI James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-293
Enclosures:
- 1. Amendment No. 232 to License No. DPR-35
- 2. Safety Evaluation cc w/encls: Distribution via ListServ DISTRIBUTION:
PUBLIC S. Bahadur, Nrr RidsOGCRp Resource RidsRgn1 MailCenter RidsNrrLASLittle M. Razzaque, Nrr RidsNrrDirsltsb Resource RidsNrrDorlDpr Resource M. Gray, RI RidsNrrPMJKim RidsNrrDssSrxb Resource RidsNrrDorlLpl1-1 Resource RidsAcrsAcnw_MailCTR Resource Accession No. ML090640224
- See memo dated March 3 2009 OFFICE LPLI-1/PM LPLI-1/LA SRXB/BC OGC LPL1-1/BC NAME
~IKim SLittie RCranston*
SUttal MKowal DATE 3/17/09 3/17/09 3/3/2009 3/18/09 3/26/09 OFFICIAL RECORD COpy